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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Fusion Science and Technology
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A more open future for nuclear research
A growing number of institutional, national, and funder mandates are requiring researchers to make their published work immediately publicly accessible, through either open repositories or open access (OA) publications. In addition, both private and public funders are developing policies, such as those from the Office of Science and Technology Policy and the European Commission, that ask researchers to make publicly available at the time of publication as much of their underlying data and other materials as possible. These, combined with movement in the scientific community toward embracing open science principles (seen, for example, in the dramatic rise of preprint servers like arXiv), demonstrate a need for a different kind of publishing outlet.
Takashi Okazaki, Takuro Honda, Yasushi Seki, Tomoaki Kunugi, Isao Aoki
Fusion Science and Technology | Volume 32 | Number 2 | September 1997 | Pages 296-303
Technical Paper | Safety/Environmental Aspect | doi.org/10.13182/FST97-A19899
Articles are hosted by Taylor and Francis Online.
The concept for a plasma shutdown system has been studied for fusion experimental reactors. An impurity pellet injection system is proposed as the plasma shutdown system. The density limit disruption is employed by using impurity pellet injection. The pellet size and its injection velocity are obtained with an evaluation model of the tearing mode and a model of pellet ablation. The main functions of the impurity pellet injection system are checked by the trial manufacturer. The concept for this plasma shutdown system is extended to the International Thermonuclear Experimental Reactor (ITER).